Calculations of Settings in the Protection and Blocking Circuits of the Power Supply System of Electromagnetic Windings and the Duration of Plasma Discharges in T-15MD Tokamak

• Published in: Physics of atomic nuclei Vol. 84; no. 7; pp. 1332 - 1341
• Main Authors: Khvostenko, P. P., Bondarchuk, E. N., Kavin, A. A., Leonov, V. M., Chudnovskiy, A. N.
• Format: Journal Article
• Language: English
• Published: Moscow Pleiades Publishing 01.12.2021; Springer; Springer Nature B.V
• Subjects: Circuit protection; Coils (windings); Configuration management; Design parameters; Discharge; Electromagnetism; Elongation; Magnetic fields; Mathematical analysis; Overheating; Particle and Nuclear Physics; Physics; Physics and Astronomy; Plasma; Plasma currents; Plasma heating; Power supply; Research facilities; Tokamak devices; Tokamaks; discharge duration; divertor configuration; magnetic system; toroidal and poloidal coils; calculation program; tokamak; water cooling system; plasma; protection and blocking system; power supply system
• ISSN: 1063-7788; 1562-692X
• DOI: 10.1134/S1063778821070061

At the present time, the construction of the T-15MD Tokamak is being completed at the National Research Center Kurchatov Institute. The magnet system of the Tokamak T-15MD should provide generation and confinement of the hot plasma in the divertor configuration. The design plasma parameters are as follows: major radius of 1.48 m, minor radius of 0.67 m, elongation of 1.7–1.9 and triangularity of 0.3–0.4, plasma current of 2 MA, toroidal magnetic field on the plasma axis of 2 T. The electromagnetic system includes toroidal and poloidal coils. The installation will be equipped with the auxiliary plasma heating and current drive in quasi-stationary discharges lasting hundreds of seconds. Scenarios of quasi-stationary plasma discharges are determined by the capabilities of the electromagnetic system to create and maintain an equilibrium magnetic configuration of the plasma column. Trouble-free operation of the power supply is provided by the protection and blocking system. This work is devoted to calculations of the maximum duration of currents in toroidal and poloidal windings in order to avoid their overheating, as well as the duration and scenarios of quasi-stationary plasma discharges.